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mcnp6
The Monte Carlo N-Particle (MCNP) radiation transport code is a Monte Carlo transport code developed by Las Alamos National Laboratory (LANL).
It supports over 37 different types of particles, and is widely used by nuclear engineers,
and nuclear physicists.
Here are 7 public repositories matching this topic...
MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
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Dec 11, 2024 - Python
POLY2TET: A Computer Program for Conversion of Computational Human Phantoms from Polygonal Mesh to Tetrahedral Mesh
geant4 phantom radiation montecarlo-simulation phits mesh-phantoms tetrahedral-mesh computational-human-phantoms mcnp6
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Apr 1, 2022 - C++
MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.
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Jul 7, 2024
Tools used for MCNP input deck syntax highlighting
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Updated
May 24, 2024 - Python
Created by Los Alamos National Laboratory
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- Website
- mcnp.lanl.gov
- Wikipedia
- Wikipedia